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Temperature Coefficient Measurements on a Critical Mock-Up of EBR-I

Description: A rough mock-up of the EBR-I reactor was built in the ZPR-III critical assembly machine, with resistance heaters in the core and inner blanket. The variation of reactivity with core temperature was observed. Lateral expansion was measured as the core was heated. A temperature coefficient of --0.42 inhour per degree Centigrade was observed when the core alone was heated, and --0.72 inhour per degree Centigrade was observed when the core and inner blanket both were heated. Essentially all of these coefficients are attributable to volume expansion. (auth)
Date: March 1, 1958
Creator: Long, J. K.
Partner: UNT Libraries Government Documents Department

CRITICAL STUDIES OF A FAST REACTOR CORE CONTAINING DEPLETED URANIUM AND SODIUM AS DILUENTS. (APR-III Assembly 36)

Description: Critical studies were performed with a metallic, fast reactor core designed to snvestigate the effects of replacing highly absorbing U/sup 238/ diluent with high-scattering, lowabsorbing sodium diluent. The fuel was 15.7 wt% enriched U/sup 235/ and the core contained 18.2 vol% sodium and 12.68 vol% stainless steel. The experimental program was designed to measure the effect of the material replacement on spectral indices, which consisted of the standard fission ratios, foil irradiations, and a large number of central reactivity coefficients. Other measurements included the Rossi- alpha , radial fission traverses, and edge reactivity worths of a few samples. (auth)
Date: January 1, 1962
Creator: Gasidlo, J.M.; Long, J.K. & McVean, R.L.
Partner: UNT Libraries Government Documents Department

CRITICAL STUDIES OF A DILUTE FAST REACTOR CORE (ZPR-III ASSEMBLY 31)

Description: Critical studies were performed on a dilute, metallic, fast reactor core. The fuel was 38.6% enriched uranium and reduced-density aluminum was used to simulate sodium coolant. The measured critical mass was 463 kg of U/sup 235/ in a 425-liter core. The main part of the experimental program consisted of measurements of the standard fission ratios, a number of central reactivity coefficients, and the prompt neutron lifetime. An additional series of experiments were performed to obtain the worths of aluminum, aluminum oxide, and sodium at various radial positions in the core. (auth)
Date: October 1, 1961
Creator: Gasidlo, J.M.; Long, J.K. & McVean, R.L.
Partner: UNT Libraries Government Documents Department

CRITICAL STUDIES OF URANIUM-STEEL AND URANIUM-STEEL-SODIUM FAST REACTOR CORES. (ZPR-III ASSEMBLIES 32 and 33

Description: S>Critical studies of two fast reactor cores are described: one contains uranium and steel; the other contains uranium, steel, and sodium. Experimental results are given for fission ratio, central and edge reactivity coefficients, fuel bunching, average prompt neutron lifetime, and distributed worth measurements. (auth)
Date: February 1, 1963
Creator: Amundson, P.I.; Gemmell, W.; Long, J.K. & McVean, R.L.
Partner: UNT Libraries Government Documents Department

A SUBCRITICAL PLUTONIUM-FUELED FAST REACTOR CORE (ZPR-III ASSEMBLY 37)

Description: A subcritical fast reactor, fueled with Pu, is described. Calculations and experimental measurements of neutron flux and gamma dose rates near the bare core face are reported, as well as the core temperature increase eaused by Pu alpha and gamma heating. (auth)
Date: July 1, 1962
Creator: Amundson, P.I.; Jiacoretti, R.; Long, J.K. & McVean, R.L.
Partner: UNT Libraries Government Documents Department

CRITICAL STUDIES OF A DILUTE OXIDE FAST REACTOR CORE (ZPR-III ASSEMBLY 30)

Description: BS>Critical studies of a fast reactor core containing a simulated oxide fuel having an oxygen-uranium atomic ratio of 1: 1 are described. Calculated and experimental critical masses are compared. Experimental results are given for fission ratio, central reactivity coefficient, fuel bunching, and distributed worth measurements. (auth)
Date: May 1, 1961
Creator: Amundson, P.I.; Hess, A.L.; Keeney, W.P.; Long, J.K. & McVean, R.L.
Partner: UNT Libraries Government Documents Department

CRITICAL STUDIES OF DILUTE CARBIDE FAST REACTOR CORE. ZPR-III Assembly 34

Description: Critical studies were made with a simulated, large, dilute power reactor having uranium carbide as fuel. The uranium in the core was 30.7% enriched, and the atomic ratio of uranium to carbon was 0.946. The critical mass was 503.01 kg U/sup 235/ and the critical volume 574.47 liters. Central reactivity coefficients, effective fission crosssection ratios, heterogeneity effects, reactivity worth of distributed materials, foil irradiations, and the average prompt neutron lifetime were measured. Multigroup calculations using the Yiftah, Okrent, and Moldauer crosssection set overestimated k for the critical configuration by 4.7%. (auth)
Date: May 1, 1961
Creator: Hubert, R.J.; Long, J.K.; McVean, R.L. & Gasidlo, J.M.
Partner: UNT Libraries Government Documents Department

CRITICAL STUDIES OF A 450-LITER URANIUM OXIDE FAST REACTOR CORE (ZPR-III ASSEMBLY 29)

Description: Results of studies with ZPR-IH Assembly 29, a mockup of a typical, dilute UO/sub 2-/-fueled fast reactor, are reported. The assembly consisted of a 454-liter cylindrical core, blanketed with depleted uranium, with a critical mass of 42l kg U/sup 235/. Experimnents included measurements of fission rates, material reactivity worths, and Rossi alpha. The results of multigroup calculations using the present Argonne cross-section sets are presented, and discrepancies between experimental results and calculations are discussed. (auth)
Date: November 1, 1960
Creator: Hess, A.L.; Gemmell, W.; Long, J.K. & McVean, R.L.
Partner: UNT Libraries Government Documents Department

TWO SPHERICAL FAST CRITICAL EXPERIMENTS (ZPR-III ASSEMBLIES 38 AND 39)

Description: Two spherical versions of earlier cylindrical assemblies were used for a critical study of shape effects for fast reactor cores with volumes of 300 to 400 liters. Assemblies 24 (cylindrical) and 38 (spherical) had a high-density metallic U blanket, whereas the set of assemblies numbered 31 (cylindrical) and 39 (spherical) had a low-density U-fueled core (with steel and Al diluents) with a highdensity blanket of depleted U. The main features of these assemblies are summarized. Reactivity coefficients of a small number of fissile and nonfissile materials were measured in both assemblies (38 and 39). In Assembly 38 the effects of environment, etc., upon fission rates measured with absolute fission chambers were investigated. Radial fission rate traverses in different directions were made in Assembly 39 to reveal any flux asymmetry due to heterogeneity of the core; no such effect was detected.(auth)
Date: July 1, 1962
Creator: Bates, J.C.; Davey, W.G.; Amundson, P.I.; Gasidlo, J.M.; Long, J.K. & Keeney, W.P.
Partner: UNT Libraries Government Documents Department

HAZARD EVALUATION REPORT ON THE FAST REACTOR ZERO POWER EXPERIMENT (ZPR- III)

Description: An evaluation was made of the hazards associated with studies of the use of U/sup 235/ as fuel in the Fast Reactor Zero Power Experiment (ZPR-III) in the design of EBR-II. The systems are blanketed cores having a range of compositions in which the volume fractions of U/sup 235/, U/sup 238/ Fe, and Na are varied. Methods used for protection against accident or damage are described. Excursions resulting if the safety mechanisms did not operate are discussed. (M.C.G.)
Date: October 1, 1961
Creator: Brittan, R.O.; Cerutti, B.; Lichtenberger, H.V.; Long, J.K.; McVean, R.L.; Thalgott, F.W. et al.
Partner: UNT Libraries Government Documents Department

Temperature distributions in a reactor fuel plate

Description: A report about the effects upon the fuel plate temperatures of introducing channel spacers into the proposed curved plate subassembly for the super critical water reactor.
Date: 1954
Creator: Redmond, R. F.; Chastain, Joel W.; Long, J. K.; Jung, R. G. & Fawcett, Sherwood L.
Partner: UNT Libraries Government Documents Department

Temperature distributions in a reactor fuel plate

Description: A report pertaining to heat-transfer characteristics , the supercritical water reactor, and flat fuel plates separated by cylindrical spacers perpendicular to the plates.
Date: 1954
Creator: Long, J. K.; Chastain, Joel W.; Redmond, R. F.; Jung, R. G. & Fawcett, Sherwood L.
Partner: UNT Libraries Government Documents Department